ML20028C918
| ML20028C918 | |
| Person / Time | |
|---|---|
| Issue date: | 11/16/1982 |
| From: | Hale C, Harrell P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028C915 | List: |
| References | |
| REF-QA-99900525 NUDOCS 8301140307 | |
| Download: ML20028C918 (15) | |
Text
.
ORGANIZATION:
GILBERT / COMMONWEALTH UTILITIES GROUP READING, PENNSYLVANIA REPORT INSPECTION INSPECTION NO.:
99900525/82-02 DATE(S) 10/5-8/82 ON-SITE HOURS: 52 CORRESPONDENCE ADDRESS:
Gilbert / Commonwealth Utilities Group ATTN:
Mr. H. Lorenz, Group Vice President Post Office Box 1498 Reading, PA 19603 ORGANIZATIONAL CONTACT:
Mr. N. R. Barker, Vice President, QA TELEPHONE NUMBER:
(215) 775-2600 PRINCIPAL PRODUCT: Architect Engineering and Consulting Services NUCLEAR INDUSTRY ACTIVITY: The total effort committed to domestic nuclear activities at the Reading facility is approximately 34% of the 2700 person staff of the Utilities Group.
Major projects include Perry, Units 1 and 2; V. C.
~
Summer, Unit 1; Three Mile Island, Unit 1 restart; and continuing services for Crystal River, Unit 3; Ginna Station; and Virginia Electric and Power Company.
r1 kAA.f D
\\2, 92, ASSIGNED INSPECTOR:
I P. F Ha W ctor Systems Section (RSS)
Date' OTHER INSPECTOR (S): C. J. Hale, RSS APPROVED BY:
8j ll!/bkb C. J. Qgye?, Chief, RSS Date INSPECTION BASES AND SCOPE:
A.
BASES:
10 CFR Part 50, Appendix B and Topical Report GAI-TR-106.
l B.
SCOPE:
Status of previous inspection findings and the following:
(1) NRC
(
Inspection Report 99900328/81-01 (Brown - Boveri, Tulsa) stating 7kV speed and transfer switches were manufactured for the V. C. Summer Station without required submission of NDE procedures and operator qualifications; (2) TVA (Watts Bar, Units 1 and 2) reported that Gilbert / Commonwealth (G/C) used (cont. on next page)
PLANT SITE APPLICABILITY:
50-395 and 50-390/391.
8301140307 821126 PDR Ch4999 EECCBAS 995N}0525 PDR
e l
ORGANIZATION:
GILBERT / COMMONWEALTH 1
UTILITIES GROUP 1
READING, PENNSYLVANIA REPORT INSPECTION l
NO.:
99900525/82-02 RESULTS:
PAGE 2 of 6 SCOPE: (Cont.) incorrect design spectra in the analysis of pipe stresses in the Emergency Raw Cooling Water System; and (3) 10 CFR Part 21 report (V. C. Summer Station) stating G/C issued an incomplete Engineering Change l
Notice for replacement of elastomers in safety-related solenoid valves.
A.
VIOLATIONS:
None B.
NONCONFORMANCES:
Contrary to the requirements of Criterion V of Appendix B of 10 CFR 50, l
procedures / instructions in effect before November 2, 1981, did not assure that all necessary and required information was included in Engineering Change Notice (ECN) 1427-FM issued for the V. C. Summer Plant.
C.
UNRESOLVED ITEMS:
None D.
STATUS OF PREVIOUS INSPECTION FINDINGS:
1.
(Closed) Nontonformance (81-03):
Revision XI of specification SP-527-4549-00 does not specifically address the material requirements for the Perry, Units 1 and 2, anchor and barrier plates of containment mechanical piping penetration assemblies as committed in G/C 10 CFR Part 21 report to NRC, dated April 28, 1981.
Specification SP-527-4549-00 has been revised to include the material requirements for the anchor and barriar plates.
An engineering design guide, engineering design bulletin, and internal memo have been issued to all engineering personnel to provide additional clarity for the design of and requirements for containment penetration anchor plates.
2.
(Closed) Nonconformance (81-03):
Design specifications 597-04-4461-00, 592-04-4461-00, and 527-4549-00 did not include all the design input data required by Section 3.0 of ANSI N45.2.11.
Specification 597-04-4461-00 has been revised to identify the proper design input.
A calculation (SP-13.19) has been performed to verify the sodium hydroxide tank will operate under the new conditions stated
ORGANIZATION:
GILBERT / COMMONWEALTH UTILITIES GROUP READING, PENNSYLVANIA REPORT INSPECTION NO.:
99900525/82-02 RESULTS:
PAGE 3 of 6 in the specification.
G/C has issued a letter to South Carolina Electric and Gas (SCE&G) recommending recertification of the tank.
Also, G/C has issued a design bulletin to remind engineering personnel to give proper consideration to tanks operating under vacuum conditions.
Specification 592-04-4461-00 has been revised to include proper operability requirements.
A procedure revision and a design bulletin have been issued to clarify use of operability requirements in specifications.
Specification 527-4549-00 has been revised to clarify the requirements for barrier and anchor plates.
In addition, the Perry Power Project FSAR has been changed to reflect the design requirements stated in the specification.
3.
(Closed) Nonconformance (81-03):
A piping system analyst did not identify, nor note on the affected system stress isometric drawing 47K-406-128, that the spatial orientation of the X-axis used in stress calculation 0600165-08-17 was reversed from conventional orientation as required by TVA procedures CEB-SQN-100 and SQN-DC-V-13.3.
Further, the checker failed to detect and record the error as required by the Sequoyah Nuclear Power Plant Checking Procedure.
l A memo has been issued to all T-PIPE users to alert them of this problem.
G/C management stated that revised procedural instructions were issued to the Oak Ridge office to preclude repetition of the error.
The procedures were not available for review at the G/C Reading office; however, an inspection of the G/C Oak Ridge office will be scheduled.
4.
(Closed) Nonconformance (81-03):
Mechanical Department calculation 13.19, dated June 11, 1981, did not note the specific purpose or objective of the calculation nor did it identify the source (s) of the negative three psi pressure differential and the atmospheric pressure variation that were used as design inputs to the calculation as required by V. C. Summer procedure 4.2.1, section 4.1.4.
The calculation has been revised to clarify the specific purpose.
A memo had been issued to strengthen enforcement of existing procedural requirements.
i l
ORGANIZATION:
GILBERT / COMMONWEALTH UTILITIES GROUP READING, PENNSYLVANIA REPORT
' INSPECTION NO.:
99900525/82-02 RESULTS:
PAGE 4 of 6 5.
(Closed) Nonconformance (82-01):
A Design Verification Status Report (DVSR) prepared by the Applied Engineering Analysis discipline did not identify and, therefore, did not indicate the status of safety-related calculation 2.7.1.2.
The DVSR has been revised to include calculation 2.7.1.2.
All affected project engineers have verified that their portion of the DVSR is complete, accurate, and up-to-date.
E.
OTHER FINDINGS OR COMMENTS:
1.
NRC Inspection Report 99900328/81-01 (Brown-Boveri, Tulsa) - This report states that 7kV speed and transfer switches were manufactured by Brown-Boveri for the V. C. Summer Station without submission of the required documents.
Specification SP-701-4461-00, Revision 2, dated October 12, 1973, requires the following documents be submitted to G/C or SCE&G for approval at least 6 weeks prior to start of manufacture:
(1) NDE procedures; (2) NDE operator qualifications; and (3) seismic calculations or test results.
Specification SP-701-4461-00 is a quality assurance program requirements generic specification.
A copy of SP-701-4461-00 is provided as an attachment to all procurement specifications; in this case, specification SP-613-04-4461-000.
The requirements stated in specification SP-701-4461-00 are reviewed by the Quality Assurance Division (QAD) to determine which documents in the generic list are required for submittal for each specific procurement.
A Manufacturer's Required Data List (MRDL) is generated as a result of the QAD review and transmitted to the contractor.
An MRDL was sent to Gould (presently known as Brown-Boveri) on May 11, 1977.
The MRDL did not require Gould to submit NDE procedures or NDE operator qualifications as a requirement to comply with specification SP-613-04-4461-000.
As noted in a G/C Expediting Report, dated June 13, 1977, documentation for seismic calculations or test results were not available for the switches being procured.
The report also states that Gould requested approval to fabricate one switch to be used for seismic testing; approval was given by G/C.
On November 23, 1977, a release for fabrication was issued by G/C with the understanding that the seismic test would be performed in parallel with fabrication activities.
The seismic test report was submitted by Gould and was approved by G/C on November 23, 1978.
The switches were also shipped on that date.
I c
ORGANIZATION:
GILBERT / COMMONWEALTH UTILITIES GROUP READING, PENNSYLVANIA REPORT INSPECTION NO.:
99900525/82-02 RESULTS:
PAGE 5 of 6 No nonconformances or unresolved items were identified concerning procurement control commitments in the G/C Quality Control Program.
2.
TVA 10 CFR 50.55(e) Report, Incorrect Design Spectra by the G/C Oak Ridge Office - The report states that the incorrect response spectra were used at several support locations.
The error was discovered by G/C during an analysis review.
At the time the error was made, G/C Oak Ridge office personnel were working under a services contract with TVA.
Within the scope of this contract, the G/C Oak Ridge office personnel worked under TVA direction and under the TVA QA program.
Therefore, the design work and verification performed by G/C personnel were controlled by requirements of the TVA QA Program.
G/C Oak Ridge office personnel have since performed TVA work under G/C direction and under the G/C quality assurance program.
Since the G/C Oak Ridge office personnel have been under control of the G/C quality assurance program, internal audits indicate that G/C has performed to the commitments of their quality program.
No nonconformances or unresolved items were identified.
This item is considered closed at G/C.
3.
A 10 CFR Part 21 Report (SCE&G) - This report states that G/C issued an ECN that did not contain a complete list of the ASCO solc.ioid-operated val,ves in the V. C. Summer Plant that required modification.
A memo from the G/C Instrumentation & Control (I&C) Section, dated December 18, 1979, requested certain tisciplines provide a list of ASCO valves in the V. C. Summer Plant containing ethylene propylene rubber elastomers.
The I&C Section was accumulating the list from each discipline to prepare the ECN.
The Mechanical / Nuclear Section returned a list providing all the ASCO valves, but the solenoid number for four of the valves was to be provided "later."
When the I&C Section received the input, they compiled a composite list of the valves as an attachment to ECN 1427-FM.
During this compilation, the ECN preparer did not include the four valves which had solenoid numbers listed as "later."
ECN 1427-FM was issued and sent to the utility (SCE&G).
A subsequent check of the list by SCE&G revealed that four valves were missing and issued a 10 CFR Part 21 report.
ORGANIZATION:
GILBERT / COMMONWEALTH UTILITIES GROUP READING, PENNSYLVANIA REPORT INSPECTION NO.:
99900525/82-02 RESULTS:
PAGE 6 of 6 G/C did not maintain a program that assured important activities were satisfactorily accomplished in that no mechanism was established to prevent the ECN from being closed when information (the solenoid number for the four valves) was still required to provide a complete list of the valves.
A nonconformance resulted from this area of inspection (see B above).
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